Letter Sequence Response to RAI |
---|
|
|
MONTHYEARML24019A0092024-01-19019 January 2024 – Application for Subsequent Renewed Operating Licenses Project stage: Request CNL-24-001, Enclosure 2: Browns Ferry Nuclear Plant Subsequent License Renewal Application Appendix E, Applicant’S Environmental Report-Operating License Renewal Stage2024-01-19019 January 2024 Enclosure 2: Browns Ferry Nuclear Plant Subsequent License Renewal Application Appendix E, Applicant’S Environmental Report-Operating License Renewal Stage Project stage: Other CNL-24-011, Application for Subsequent Renewed Operating Licenses, Supplemental Information - Neutron Fluence Analyses Methodology2024-01-22022 January 2024 Application for Subsequent Renewed Operating Licenses, Supplemental Information - Neutron Fluence Analyses Methodology Project stage: Supplement ML24079A1562024-04-0505 April 2024 Notice of Intent to Prepare an Environmental Impact Statement and Conduct Scoping Process Project stage: Other ML24078A2722024-04-10010 April 2024 Subsequent License Renewal Public Scoping Meeting Project stage: Meeting ML24123A1572024-04-11011 April 2024 Transcript of April 11, 2024 Browns Ferry Public Scoping Meeting, Pages 1-45 Project stage: Request PMNS20240393, Environmental Scoping Meeting Related to the Browns Ferry Power Plant License Renewal Application2024-04-11011 April 2024 Environmental Scoping Meeting Related to the Browns Ferry Power Plant License Renewal Application Project stage: Meeting ML24155A0432024-04-18018 April 2024 Meeting Summary Project stage: Meeting ML24123A1622024-04-18018 April 2024 Transcript of April 18, 2024 Browns Ferry Public Scoping Meeting, Pages 1-28 Project stage: Request PMNS20240394, Environmental Scoping Meeting Related to the Browns Ferry Power Plant License Renewal Application2024-04-18018 April 2024 Environmental Scoping Meeting Related to the Browns Ferry Power Plant License Renewal Application Project stage: Meeting ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter Project stage: Other ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter Project stage: Other ML24155A0422024-06-13013 June 2024 Meeting Summary: Public Scoping Webinars for the Environmental Review of the Subsequent License Renewal Application for Browns Ferry Nuclear Plant, Units 1, 2, and 3 Project stage: Meeting ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) Project stage: Approval ML24239A3332024-09-0303 September 2024 Full Audit Plan Project stage: Other CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 Project stage: Response to RAI 2024-04-18
[Table View] |
|
---|
Category:Letter type:CNL
MONTHYEARCNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-013, Cycle 22 Reload Analysis Report2024-03-14014 March 2024 Cycle 22 Reload Analysis Report CNL-24-026, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 CNL-24-011, Application for Subsequent Renewed Operating Licenses, Supplemental Information - Neutron Fluence Analyses Methodology2024-01-22022 January 2024 Application for Subsequent Renewed Operating Licenses, Supplemental Information - Neutron Fluence Analyses Methodology CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472023-07-0303 July 2023 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . CNL-23-046, Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal2023-06-0606 June 2023 Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-034, 10 CFR 50.46 Annual Report2023-04-26026 April 2023 10 CFR 50.46 Annual Report CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-018, Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)2023-03-30030 March 2023 Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report CNL-23-027, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524)2023-03-29029 March 2023 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524) CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-23-021, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-03-0808 March 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023 Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-23-008, Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-12-22022 December 2022 Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) 2024-09-24
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARCNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 CNL-24-026, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .2022-12-0101 December 2022 Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide . CNL-22-075, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.2022-09-12012 September 2022 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,. CNL-22-065, Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.2022-08-0101 August 2022 Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie. CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-007, Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)2022-04-0606 April 2022 Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518) CNL-22-028, Response to Request for Additional Information Regarding License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)2022-03-18018 March 2022 Response to Request for Additional Information Regarding License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534) CNL-21-052, Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531)2021-07-21021 July 2021 Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531) CNL-21-033, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components2021-04-28028 April 2021 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components CNL-21-017, Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099)2020-12-29029 December 2020 Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099) CNL-20-089, Response to RAI Re Application for Tech. Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-518)2020-12-21021 December 2020 Response to RAI Re Application for Tech. Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-518) CNL-20-059, Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals2020-08-10010 August 2020 Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals CNL-19-122, Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights2019-12-17017 December 2019 Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights CNL-19-064, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water...2019-08-0808 August 2019 Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water... CNL-19-052, Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second2019-07-19019 July 2019 Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second CNL-19-017, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information2019-01-25025 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information CNL-19-007, Supplement 5, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus2019-01-16016 January 2019 Supplement 5, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus CNL-19-011, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results2019-01-16016 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results CNL-18-139, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information2018-12-14014 December 2018 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information CNL-18-140, Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 42018-12-13013 December 2018 Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 4 CNL-18-117, Response to Request for Additional Information Regarding Browns Ferry Units 1, 2, and 3: Code Case N-702 for Alternative Request ISI-462018-10-17017 October 2018 Response to Request for Additional Information Regarding Browns Ferry Units 1, 2, and 3: Code Case N-702 for Alternative Request ISI-46 CNL-18-120, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-year ..2018-10-11011 October 2018 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-year ... ML18283A8972018-10-10010 October 2018 Enclosure 1: Proposed Changes to Browns Ferry Nuclear Plant Unit 1 Technical Specifications, Attachments 1, 2, & 3 CNL-18-089, Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-0342018-07-23023 July 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-034 CNL-18-044, Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation.2018-04-19019 April 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation. NL-18-044, Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Pre2018-04-19019 April 2018 Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Prec CNL-18-032, Tennessee Valley Authority Response to NRC Request for Additional Information (Set 2) Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program2018-03-27027 March 2018 Tennessee Valley Authority Response to NRC Request for Additional Information (Set 2) Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program CNL-18-011, Tennessee Valley Authority Response to NRC Request for Additional Information Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497)2018-02-0505 February 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497) CNL-17-130, Update to Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection For..2017-10-23023 October 2017 Update to Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection For.. CNL-17-109, Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Genera2017-09-18018 September 2017 Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generati CNL-17-098, Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-27027 July 2017 Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-085, Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-0707 July 2017 Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-039, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory..2017-03-10010 March 2017 Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory.. CNL-17-035, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate(Epu) - Supplement 38, Spent Fuel Pool Criticality Safety Analysis - Updated Information2017-03-0303 March 2017 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate(Epu) - Supplement 38, Spent Fuel Pool Criticality Safety Analysis - Updated Information CNL-17-017, Proposed Technical Specifications (TS) Change TS-505 Request for License Amendments - Extended Power Uprate (EPU) - Supplement 37, Transmission System Update - Environmental Aspects2017-02-0303 February 2017 Proposed Technical Specifications (TS) Change TS-505 Request for License Amendments - Extended Power Uprate (EPU) - Supplement 37, Transmission System Update - Environmental Aspects CNL-17-015, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects2017-01-20020 January 2017 Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects NL-17-015, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Saf2017-01-20020 January 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safe CNL-16-196, Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-12-19019 December 2016 Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools CNL-16-161, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 33, Revised Response to Request for Additional..2016-10-13013 October 2016 Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 33, Revised Response to Request for Additional.. CNL-16-145, Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 302016-09-23023 September 2016 Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 30 CNL-16-150, Revised Response to Requests for Additional Information Proposed Technical Specifications Change TS-505 - Request for License Amendment - Extended Power Uprate - Supplement 312016-09-21021 September 2016 Revised Response to Requests for Additional Information Proposed Technical Specifications Change TS-505 - Request for License Amendment - Extended Power Uprate - Supplement 31 CNL-16-133, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 72016-09-15015 September 2016 Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 7 CNL-16-152, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 32, Revised Responses to Requests for Additional Information2016-09-12012 September 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 32, Revised Responses to Requests for Additional Information CNL-16-126, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486)2016-08-24024 August 2016 Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) 2024-03-14
[Table view] |
Text
1101 Market Street, Chattanooga, Tennessee 37402
CNL-24-077
October, 2024
10 CFR 54
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information 6HW (EPID: L-2024-SLE-0000)
Reference:
- 1. Letter from TVA to NRC, CNL-24-001, "Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Application for Subsequent Renewed Operating Licenses," dated January 19, 2024 (ML24019A010)
- 2. Letter from TVA to NRC, CNL-24-011, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Application for Subsequent Renewed Operating Licenses, Supplemental Information - Neutron Fluence Analyses Methodology, dated January 22, 2024 (ML24022A292)
- 3. NRC electronic mail to TVA, Browns Ferry SLRA - Request for Additional Information - Set #1, dated September 10, 2024 (ML24255A458)
By Reference 1, the Tennessee Valley Authority (TVA) submitted a subsequent license renewal application (SLRA) for the Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3, Renewed Facility Operating Licenses in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants. By Reference 2, TVA provided the first supplement to the SLRA.
Since March 2024, TVA has been engaged with the Nuclear Regulatory Commission (NRC) staff in the safety audit of the SLRA. This audit has resulted in a request for additional information (RAI) (Reference 3). The TVA RAI response is provided in the enclosure to this letter.
U.S. Nuclear Regulatory Commission CNL-24-0 Page 2 October, 2024
There are no new regulatory commitments in this letter. Should you have any questions regarding this submittal, please contact Peter J. Donahue, Director, Subsequent License Renewal, at pjdonahue@tva.gov.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this th day of October 2024.
Respectfully, Digitally signed by Edmondson, Carla Date: 2024.10.09 09:58:19 -04'00' Kimberly D. Hulvey General Manager, Nuclear Regulatory Affairs and Emergency Preparedness
Enclosure:
Response to Request For Additional Information by the Office Nuclear Reactor Regulation Browns Ferry Nuclear Plant, Units 1, 2, and 3 SLRA Docket Nos. 05000259, 05000260, 05000296 Issue Date: 09/10/2024
cc:
NRC Regional Administrator - Region II NRC Branch Chief - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager, License Renewal Projects Branch (Safety)
State Health Officer, Alabama Department of Public Health (w/o Enclosure)
Enclosure
Response to Request For Additional Information by the Office Nuclear Reactor Regulation Browns Ferry Nuclear Plant, Units 1, 2, and 3 SLRA Docket Nos. 05000259, 05000260, 05000296 Issue Date: 09/10/2024 Enclosure
The Nuclear Regulatory Commission (NRC) Request for Additional Information provided the following background discussion.
Regulatory Basis
10 CFR 54.21(a)(3) requires an applicant to demonstrate that the effects of aging for structures and components will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation. One of the findings that the staff must make to issue a renewed license (10 CFR 54.29(a)) is that actions have been identified and have been or will be taken with respect to managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21, such that there is reasonable assurance that the activities authorized by the renewed license will continue to be conducted in accordance with the current licensing basis. In order to complete its review and enable making a finding under 10 CFR 54.29(a), the staff requires additional information in regard to the matters described below.
RAI B.2.1.27-1
Background:
GALL-SLR Report AMP XI.M41, Buried and Underground Piping and Tanks, Table XI.M41 -1, Preventive Actions for Buried and Underground Piping and Tanks, recommends that cathodic protection is provided for buried steel piping. In addition, GALL-SLR Report AMP XI.M41 states the following:
x [f]ailure to provide cathodic protection in accordance with Table XI.M41-1 may be acceptable if justified in the SLRA. The justification addresses soil sample locations, soil sample results, the methodology and results of how the overall soil corrosivity was determined, pipe to soil potential measurements and other relevant parameters. If cathodic protection is not provided for any reason, the applicant reviews the most recent 10 years of plant-specific operating experience (OE) to determine if degraded conditions that would not have met the acceptance criteria of this AMP have occurred. This search includes components that are not in -scope for license renewal if, when compared to in -scope piping, they are [of] similar materials and coating systems and are buried in a similar soil environment. The results of this expanded plant -specific OE search are included in the SLRA.
x [a]dditional inspections, beyond those in Table XI.M41-2 [Inspection of Buried and Underground Piping and Tanks] may be appropriate if exceptions are taken to program element 2, preventive actions, or in response to plant-specific OE.
Exception No. 1 to SLRA Section B.2.1.27, Buried and Underground Piping and Tanks, documents the basis for why the installation of a cathodic protection system to protect buried steel piping is impractical at Browns Ferry Nuclear Plant (BFN). In addition, based on its review of SLRA Section B.2.1.27, the staff noted six inspections of buried steel piping will be conducted in each 10-year interval, consistent with Preventive Action Category E defined in GALL -SLR Report Table XI.M41-2 (adjusted for a three -unit site). Furthermore, SLRA Section B.2.1.27 states the following:
CNL-24-077 E 1 of 13 Enclosure
x based on review of BFN-specific operating experience, no leaks in the subject buried piping due to external corrosion have been observed and no significant buried piping coating degradation has been observed.
x [f]rom the 2009 soil sample APEC [Area Potential Earth Current] survey there were 6 recommended inspection locations that could possibly reflect localized areas of potential coating damage and active corrosion. It was recommended that these locations be excavated and directly inspected. There were also 6 locations recommended for excavation and direct examination based on the 8 soil samples from 2023 combined with the 48 total native potential measurements recorded as CIS [Close Interval Survey].
During its audit, the staff noted several instances of buried piping leaks and an instance of buried piping not being coated in accordance with design specifications. The first three examples below are related to buried service air piping (not in -scope based on the systems listed in SLRA Section B.2.1.27 (page B -119)) and the 4th and 5th examples are related to buried fire protection piping (in -scope based on the systems listed in SLRA Section B.2.1.27 (page B-119)).
- 1. The staff reviewed CR 793555 and noted the suspected cause of the leak was corrosion similar to that seen in two service air piping leaks earlier in 2013.
- 2. The staff reviewed CR 1120048 and noted the source of the leak was determined to be service air and not fire protection.
- 3. The staff reviewed CR 898407 and noted (a) a section of service air piping had no visible exterior tape coating or polyethylene coating as required by design drawings; and (b) the uncoated section of piping had multiple thru wall holes.
- 4. The staff reviewed CR 828934 and noted it was indeterminate whether the leak was coming from a slipjoint between sections of pipe or a hole in the pipe wall.
- 5. The staff reviewed CR 1102016 and noted that a contributing cause of a break in buried fire protection piping was outer diameter graphitic corrosion. The staff noted that although managing loss of material due to graphitic corrosion is not within the scope of the Buried and Underground Piping and Tanks program, it does provide evidence that in -scope buried steel piping is potentially exposed to an aggressive environment.
During its audit, the staff reviewed SL -016653, Evaluation of Cathodic Protection for Buried Piping, which noted that a site -wide impressed current cathodic protection (ICCP) system is not likely to be successful; however, it also notes that protecting a small scope of buried piping that is high-risk due to the pipe construction, process fluid, or the soil conditions in the area is likely achievable. The staff also reviewed BP -2023-0027-03-TR, Browns Ferry License Renewal Buried Piping Cathodic Protection Review, which provides a similar discussion.
Issue:
During its audit, the staff noted several instances of leaks and an instance of buried piping not being coated in accordance with design specifications. It is the staffs understanding that the OE described in the CRs above did not involve in -scope buried steel piping; however, the staff seeks additional information with respect to why the condition of piping documented in theses CRs is not representative of the condition of in -scope buried steel piping.
The staff recognizes that installation of a site -wide ICCP system is likely impractical at BFN.
However, based on its review of SL -016653 and BP-2023-0027-03-TR, it appears that protecting a limited scope of high -risk in-scope buried steel piping may be practical. The staff
CNL-24-077 E 2 of 13 Enclosure
seeks additional information with respect to why providing cathodic protection for a limited scope of high -risk in-scope buried steel piping is considered impractical.
The 2009 and 2023 soil surveys referenced above recommended six inspection locations that could possibly reflect localized areas of potential coating damage and active corrosion. The staff noted that this also corresponds to the recommended number of inspections for Preventive Action Category E in GALL -SLR Report Table XI.M41 -2 (adjusted for a three -unit site). Since coatings are the only barriers to aging at BFN, and coatings will continue to degrade over time, the staff seeks additional information with respect to why increased inspection quantities (beyond those prescribed in GALL -SLR Report Table XI.M41-2) are not necessary to provide reasonable assurance that loss of material on the external surfaces of in -scope buried steel piping will be adequately managed during the subsequent period of extended operation.
Request:
Provide additional information documenting the basis for why the condition of piping documented in the CRs above is not representative of the condition of in -scope buried steel piping. Include a discussion of the following as a minimum:
- 1. Similarities or differences in materials of construction for (a) in -scope buried steel piping; (b) buried service air piping referenced in the CRs above; and (c) buried fire protection piping referenced in the CRs above.
- 2. Similarities or differences in external coating types used for (a) in -scope buried steel piping; (b) buried service air piping referenced in the CRs above; and (c) buried fire protection piping referenced in the CRs above.
- 3. Similarities or differences in soil corrosivity in the vicinity of (a) in -scope buried steel piping; (b) buried service air piping referenced in the CRs above; and (c) buried fire protection piping referenced in the CRs above.
- 4. Detailed results of inspections of in -scope buried steel piping, including whether the piping was externally coated in accordance with design specifications.
Provide additional information documenting the basis for why providing cathodic protection for a limited scope of high -risk in-scope buried steel piping is considered impractical.
Based on plant-specific OE and the absence of cathodic protection, state the basis for why increased inspection quantities (beyond those prescribed in GALL -SLR Report Table XI.M41-2) are not necessary to provide reasonable assurance that loss of material on the external surfaces of in-scope buried steel piping will be adequately managed during the subsequent period of extended operation.
TVA Response
Additional information on the referenced condition reports (CR).
CR 793554 - Initiated 10/15/2013 and CR 1120048 - Date Reported: 12/30/2015
Note: CR 793555 was referenced above. We believe this to be a typo. CR 793554 refers to a piping failure.
CNL-24-077 E 3 of 13 Enclosure
These CRs discuss the same break in service air pipe. Work order (WO) 117468008 was generated to fix the leak, which was cancelled to WO 115193847. WO 115193847 was to install temporary repairs and be worked concurrent with WO 118320795 for permanent repairs and WO 114394625 to inspect the pipe. According to the work performed in WO 118320795, once the crew excavated the pipe, they found a through-wall leak in the piping and the piping was also broken at the penetration to the intake building. Repairs could not be completed due to many obstructions (other piping, bus ducts, etc.). Temporary repairs were completed and permanent repairs are pending an engineering change. CRs 1860563 and 1854648 were generated. The pipe material was carbon steel and the coating was polyethylene. The buried piping engineer was present and performed an inspection and determined the cause of the through-wall leak was internal corrosion.
CR 898407 - Date Reported: 06/13/2014
Service air leak located on a berm on the south side of the reactor building. This piping had multiple through-wall leaks and was uncoated. The suspected cause for the leak is corrosion where a small portion of the pipe was not coated. The uncoated piping was all excavated back to coated piping and replaced. The replacement piping was factory coated with polyethylene and the fittings were field coated with Tapecoat.
CR 828934
On January 6, 2014, Fire Operations identified a greater than 100 gallons per minute leak in fire protection (FP) system at the west end of cooling tower #2. Valve 0-26-1019-2 was isolated which stopped the leak. The pipe was replaced under WO 115412546. The pipe was circumferentially cracked. A heavy load above ground caused this pipe failure, likely due to unintended vehicle traffic.
CR 1102016
On November 7, 2015, a leak was discovered on a 14 high pressure fire protection pipe. The CR states that the direct cause of this failure was due to heavy external loading due to vehicular (crane) traffic. Minimum wall analysis was performed on this pipe as part of the failure mechanism analysis, and it determined that even in the areas of greatest selective leaching, there were 292 mils of wall remaining, which is above the minimum wall required thickness of 65 mils. Assuming a linear wear rate based on the age of the component, this pipe would have a remaining service life of an additional 42 years with selective leaching. It is critical to note that the minimum wall thickness is based on the piping design. Because the component had sufficient minimum wall with selective leaching, it would have been able to meet its intended function. However, by design, the component was not intended to be exposed to external forces due to heavy vehicular traffic. Therefore, the applicable minimum wall design criteria was not sufficient for this unforeseen external loading. The selective leaching present on this component was still within design margin and within allowable corrosion.
CNL-24-077 E 4 of 13 Enclosure
Request 1
Similarities and Differences in Piping Material
Table 1 - Similarities and Differences in Piping Material
CR# System Piping Type Similarities to In-Scope Material Differences from In-Scope Piping Piping 793554 / Service Air Carbon SA piping is small bore CS; The difference between the buried 1120048 (SA) Steel in-scope piping contains SA piping and buried in-scope CS (CS) carbon steel. piping is the quality control. In-scope CS piping is mostly designed to B31.1.0, Section 1, 1967. SA piping is considered run-to-failure and is not code regulated.
898407 Service Air Carbon SA piping is small bore CS; The difference between the buried Steel in-scope piping contains SA piping and buried in-scope CS carbon steel. piping is the quality control. In-scope CS piping is mostly designed to B31.1.0, Section 1, 1967. SA piping is considered run-to-failure and is not code regulated.
828934 Fire Grey This piping is in-scope; The FP segments covered in Protection Cast however, it is managed with CR 828934 are constructed of Iron NFPA 25 in accordance with cement lined grey cast iron. Non-FP Generic Aging Lessons in-scope piping is CS piping Learned for Subsequent designed to B31.1.0.
License Renewal (GALL-SLR) XI.M41.
1102016 Fire Grey This piping is in-scope; The FP segments covered in CR Protection Cast however, it is managed with 1102016 are constructed of cement Iron NFPA 25 in accordance with lined grey cast iron. Non-FP in-scope GALL-SLR XI.M41. piping is CS piping designed to B31.1.0.
CNL-24-077 E 5 of 13 Enclosure
Request 2:
Similarities and Differences in Coating Type
Table 2 - Similarities and Differences in Coating Type
CR# System Coating Type Similarities to In-Scope Differences from In-Scope Piping Piping 793554 / Service Air Some are None, SA pipe is generally 1. SA has polyethylene 1120048 coated with coated with polyethylene, and coating while in-scope Tapecoat and tape coated at the fittings and carbon steel piping has Polyethylene welds. The leak locations multi-layer coating system coatings; based were not coated. as specified by AWWA on descriptions, C203-66 A1.5.
the piping was 2. The major difference is uncoated in that the SA piping was not failure locations. coated at the leak locations.
- 3. In-scope piping was holiday tested per above coating specification. The SA piping, with sections uncoated, had not been holiday tested; otherwise, uncoated sections would have been discovered.
- 4. The SA piping is run-to-failure.
898407 Service Air Section of pipe None, SA pipe is generally 1. SA has polyethylene was not coated coated with polyethylene, and coating while in-scope per G-55 tape coated at the fittings and carbon steel piping has specification. welds. The leak locations were multi-layer coating system not coated. as specified by AWWA C203-66 A1.5.
- 2. The major difference is that the SA piping was not coated at the leak locations.
- 3. In-scope piping was holiday tested per above coating specification. The SA piping, with sections uncoated, had not been holiday tested; otherwise, uncoated sections would have been discovered.
- 4. The SA piping is run-to-failure.
CNL-24-077 E 6 of 13 Enclosure
CR# System Coating Type Similarities to In-Scope Differences from In-Scope Piping Piping 828934 Fire Coal-tar Varnish FP piping is considered FP piping, built in Protection in-scope; however, it is accordance with NFPA 24, managed with NFPA 25 in has coal tar varnish coating.
accordance with GALL-SLR Carbon steel in-scope piping XI.M41. It is coated with coal has a multi-layer coating tar varnish. There are no system as specified by similarities between FP AWWA C203-66 A1.5.
coatings and the other in-scope piping.
1102016 Fire Coal-tar Varnish FP piping is considered FP piping, built in Protection in-scope; however, it is accordance with NFPA 24, managed with NFPA 25 in has coal tar varnish coating.
accordance with GALL-SLR Carbon steel in-scope piping XI.M41. It is coated with coal has a multi-layer coating tar varnish. There are no system as specified by similarities between FP AWWA C203-66 A1.5.
coatings and the other in-scope piping.
In-scope carbon steel piping externa l coatings are the AWWA C203-66 A1.5 multi-layer coal tar with asbestos wrap coating that have seen very little degradation in buried environments. It is important to note that the service air piping referenced in the CRs is not in-scope of license renewal and is commercial, so it did not have the same rigor of configuration controls during construction. In-scope piping was tested for holidays at the time of installation.
Fire protection piping is a coal tar varnish, which is widely used in the US nuclear fleet. While fire protection piping is coated in accordance with a different standard than the coating used for in-scope carbon steel piping, the two fire protection piping failures noted were primarily caused by above ground traffic, rather than corrosion.
CNL-24-077 E 7 of 13 Enclosure
Request 3
Similarities and Differences in Soil Environment
Table 3 - Similarities and Differences in Soil Environment
CR# System Soil Environment Characterization Similarities to In-Scope Differences from In-Scope Piping Piping 793554 / Service Air Native Soil. Similarities are based on 1. Soil analysis performed for 1120048 No characterization a visual observation of in-scope piping shows available. No the soil during the moderate corrosivity according previous soil sample excavation of SA piping to criteria provided in Electric was taken from this and described as native Power Research Institute location. clay with sand mix (EPRI) Report 3002005294.
Characterization was backfill for both in-scope No soil data obtained not determined to be and SA piping. specifically for SA/FP piping.
necessary at the 2. TVA General Engineering time of inspection Specification G-9 applies to due to run-to-failure in-scope piping and specifies status. No in-scope bedding, compaction, piping is in this allowable granular material location, so no soil size, and testing. Controls on sampling was backfill for run-to-failure SA performed in piping are not documented.
preparation for SLR As stated above, varying one in this area. Higher or more soil parameters can scrutiny of backfill affect corrosivity. A visual was used for observation of the soil / backfill in-scope piping is likely not capable of system install. determining the corrosivity in the vicinity of the SA piping leaks. A visual description of the soil cannot be directly equated to soil corrosivity since the source of the native clay and sand likely does not have the same quality controls.
More importantly, the remaining soil factors related to corrosivity are unknown for SA piping. Sample ID #2 from the 2009 soil survey, Table 1 GSE report BP-2023-0027 TR, is an example of the effect one soil characteristic
(% gravel) can have on corrosivity.
CNL-24-077 E 8 of 13 Enclosure
CR# System Soil Environment Characterization Similarities to In-Scope Differences from In-Scope Piping Piping 898407 Service Air Native Soil. Similarities are based on 1. Soil analysis performed for No characterization a visual observation of in-scope piping shows available. No the soil during the moderate corrosivity according previous soil sample excavation of SA piping to criteria provided in EPRI was taken from this and described as native Report 3002005294. No soil location. clay with sand mix data obtained specifically for Characterization was backfill for both in-scope SA/FP piping.
not determined to be and SA piping. 2. TVA General Engineering necessary at the Specification G-9 applies to in-time of inspection scope piping and specifies due to run-to-failure bedding, compaction, status. No in-scope allowable granular material piping is in this size, and testing. Controls on location, so no soil backfill for run-to-failure SA sampling was piping are not documented.
performed in As stated above, varying one preparation for SLR or more soil parameters can in this area. Higher affect corrosivity. A visual scrutiny of backfill observation of the soil / backfill was used for is likely not capable of in-scope piping determining the corrosivity in system install. the vicinity of the SA piping leaks. A visual description of the soil cannot be directly equated to soil corrosivity since the source of the native clay and sand likely does not have the same quality controls.
More importantly, the remaining soil factors related to corrosivity are unknown for SA piping. Sample ID #2 from the 2009 soil survey, Table 1 GSE report BP-2023-0027 TR, is an example of the effect one soil characteristic
(% gravel) can have on corrosivity.
828934 Fire Native Soil. FP piping is considered Soil analysis performed for Protection No characterization in-scope; however, it is in-scope piping shows available. No managed with NFPA 25 moderate corrosivity according previous soil sample in accordance with to criteria provided in EPRI was taken from this GALL-SLR XI.M41. Report 3002005294. No soil environment. Backfill has been data obtained specifically for Characterization was described as native clay. SA/FP piping.
not determined to be necessary at the time of inspection.
CNL-24-077 E 9 of 13 Enclosure
CR# System Soil Environment Characterization Similarities to In-Scope Differences from In-Scope Piping Piping 1102016 Fire No characterization FP piping is considered Soil analysis performed for Protection available. in-scope; however, it is in-scope piping shows managed with NFPA 25 moderate corrosivity according in accordance with to criteria provided in EPRI GALL-SLR XI.M41. Report 3002005294. No soil Backfill has been data obtained specifically for described as native clay. SA/FP piping.
The safety related in-scope piping was surrounded with sand before the native fill was added in accordance with TVA General Engineering Specification G-9, Earth and Rock Foundation and Fills During Construction, Modification, and Maintenance for Nuclear Plants (Quality-Reviewed Document). In the pictures of the service air piping and high-pressure fire protection piping, it appears that very little sand was added, if any. All soil sampling was performed in accordance with the criteria provided in EPRI Report 3002005294.
Request 4
Detailed Inspection Results of In-Scope Buried Steel Piping
Coatings have been effective in protecting in-scope buried piping from degradation. The few instances of piping degradation that have occurred were caused by internal corrosion or mechanical damage. Site-specific operating experience (OE) shows that the coatings are effective, including internal and external piping inspections, representative soil samples taken for SLR efforts showing non-aggressive soil at piping depth, and the Area Potential Earth Current (APEC) survey. To date, no coating degradation has been found on in-scope steel buried pipe which would require an extent of condition evaluation. No external corrosion has been observed on in-scope steel buried pipe.
- 1. 24 residual heat removal service water (RHRSW) WO 10-710139-000/ BFN-1-PIPE-023/0-23003-24-01-BA and 18 emergency equipment cooling water (EECW) WO 10-710139-000/
BFN-1-PIPE-077/0-77004-14-02-AC piping was inspected and showed coating coal ta r with asbestos wrap in accordance with AWWA C203-66 A1.5. This inspection was completed in 2010. The coating was in excellent condition with minor damage attributed to excavati on activity. This location corresponds to Structural In tegrity Associates APEC survey location 6, which is between recommended locations 9 and 12. This excavation was performed as proof that the coatings systems are robust and in tact.
- 2. Standby Gas Treatment (SBGT) WO 112417467 and 115363058 follow-up inspectio n/repair for leak in 2015. The process fluid for this line is gaseous. Gravel was found in the SBGT equipment/piping, indicating the issue. The pipe was found to be separat ed at a mechanical joint where the pipe penetrates the reactor building. The cause of the separation app eared to be 7 inches of pipe settlement due to ground movement. When the penetration issue was identified, ultrasonic testing (UT) was performed, and no minimum wall issues were f ound.
Coating was well adhered to the gen eral piping, but at the location where the pipe jo int was separated by settling, the outer layer of tape was noted as found partially disbonded. The coal tar was well-adhered and no bare metal was exposed. The coating was found in accordance with AWWA C203-66 A1.5. Leakage appears to be at a partially separated joint caused by extensive settling. Numerous photos were taken of the completely intact and seemingly unchanged coating. It is important to note that the excavation area was open for
CNL-24-077 E 10 of 13 Enclosure
at least four months prior to the coating inspection being performed, and the as-found condition was not documented. The inspected area showed no evidence of pipe depressions (dimples) and welds did not show signs of degradation.
Why providing cathodic protection for a limited scope of high-risk in-scope buried steel piping is considered impractical:
As described in SL-016653, a distributed anode bed system requires up to 20 anode beds at 20 foot depth, with each anode bed comprised of ten 18-inch anode columns, spaced 20 feet apart.
This requires long lengths of cable trenching to connect the system together.
The specific issue with BFN implementing this design is the arrangement of the plant piping.
The site is located between the plant and the river/canal; the congested piping in this area includes RHRSW, EECW, fire protection, raw water, and other buried commodities. These lines are nested in some locations, with many lines in close proximity and some routed perpendicular to each other. There are other barriers such as buildings, duct banks, and paved areas making it very difficult to locate the distributed anode. Given the shielding effect of these structures and configured piping, cathodic currents would be prevented from reaching sections of targeted piping.
Protecting the entire site with this system would be impractical due to the large number of anodes and related trenching and excavations. Stray current would need to be evaluated for its effect on existing plant structures. As noted above, piping systems at BFN are in very close proximity to each other, which would make separating out a small scope of targeted piping problematic and impractical. The challenges with this design at BFN include properly locating anodes, shielding, and stray current corrosion. Stray current corrosion would adversely affect metals in the ground which are not bonded to the proposed cathodic protection (CP) system, including piping, structures, etc. Stray current corrosion is a phenomenon in which non-bonded metal within the influence of the anodes becomes anodic itself and corrodes at a faster rate than it would otherwise. Fire protection piping, as well as any piping or metallic structures not bonded to the proposed CP system, would be negatively affected by stray current corrosion. As previously discussed in the application, the fire protection piping cannot be bonded to the CP system because it is not electrically continuous.
The decision to design BFN without cathodic protection was the recommendation of TVAs Cathodic Protection Task Force, instead relying on robust coatings, painting, and proper selection of material for corrosion protection. To date, BFN Nuclear Energy Institute 09-14 Buried Pipe Program has not identified a limited scope of high-risk (i.e., susceptibility to degradation and consequences of failure), in-scope, buried steel piping. Impracticalities include shielding, nested piping, stray current corrosion, and anode bed placement.
The installation of a CP system is still impractical, and though it may be possible for a hypothetical small scope of targeted piping, any potential benefit would be far outweighed by the challenges (shielding, nested piping, and anode placement) and would cause adverse effects (stray current corrosion).
CNL-24-077 E 11 of 13 Enclosure
Describe why increased inspection quantities (beyond those prescribed in GALL-SLR Report Table XI.M41-2) are not necessary to provide reasonable assurance that loss of material on the external surfaces of in-scope buried steel piping will be adequately managed during the subsequent period of extended operation:
BFN will be using the corrective action program in accordance with Element 7 of the Buried Pipe Aging Management Program (AMP) and Operating Experience in accordance with Element 10 of the Buried Pipe AMP to inform inspections, in addition to AMP guidance. If, when initial inspections are performed, age-related degradation is found, the location will be repaired or replaced, and the number of inspections will be increased in accordance with guidance in the AMP, which is consistent with GALL-SLR.
In GALL-SLR XI.M41 Element 7, Corrective Actions, coating degradation alone does not necessitate additional inspections. BFN has not observed any coating degradation that was not excavation-induced with in-scope piping. If coating degradation is caused by the backfill, an extent of condition evaluation is performed to determine the extent of degraded backfill. All of the in-scope piping backfill has been satisfactory. Soil surveys show moderate corrosivity by EPRI standards noted in report #3002005294, with more threatening reagents such as chlorides below the low level recording limits.
The APEC survey indicates a current draw, which could be indicative of many things, including (but not limited to) coating transitions, coating flaws, or external corrosion. Several of the locations in the APEC survey were followed up on with visual inspection, UT, and guided wave UT, and no coating degradation or external corrosion was found. In-scope piping and out-of-scope piping was inspected based on APEC results. One location was excavated based on APEC results. No issue was found at the indicated location; however, guided wave UT indicated a feature outside of the excavation requiring disposition. The excavation was expanded and a failed weld, which had initiated from the inside diameter of the pipe, was discovered when the pristine coating was removed. The coating was still very much intact. This occurred on out-of-scope piping in the vicinity of APEC inspection location 1, which corresponds to recommendation location 7 from Table B.2.1.27-1. The other instances found coating transitions from factory-applied coating to field-applied coating. For these inspections, coating was removed at the transitions to ensure the substrate was not corroded, and the rest of the coating was inspected. No issues were found.
In addition to site-specific OE, industry experience is also monitored. Other sites have the same type of AWWA C203-66 A1.5 coating on their in-scope buried piping. If age-related degradation is reported, BFN will evaluate the OE in the corrective action program and modify the AMP accordingly.
BFNs OE with in-scope buried piping and the compact nature of the three-unit site does not indicate that increased inspections beyond those prescribed in Table XI.M41-2 are necessary.
The GALL-SLR program is generic to be applicable to the entire US industry. BFN has more common building usage and a more congested piping layout when compared with other, more geographically-independent, multi-unit sites, which leads to the inspections being more representative of the site (i.e., more piping in the direct vicinity of soil sample locations, etc.).
Results of the direct inspection, as evaluated in the corrective action program, will dictate future actions. If aging degradation is found, the corrective action process will determine if additional inspections are necessary for bounding an extent of condition. Inspections will be performed by a qualified coatings inspector and will be performed in accordance with the requirements described in SLRA Section B.2.1.27. The positive plant OE, current direct inspection plans, soil
CNL-24-077 E 12 of 13 Enclosure
sampling, and robust coatings provide adequate aging management and reasonable assurance that in-scope buried piping and components will perform their intended function during the subsequent period of extended operation. BFN will follow GALL-SLR XI.M41 Element 7 and Element 10 to determine if additional inspections are necessary as information is available.
CNL-24-077 E 13 of 13